• Title/Summary/Keyword: ${\gamma}$-ray radiography

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Convergence Modeling and Reproduction of a Bigyeokjincheolloe (Bomb Shell) Based on Three-dimensional Scanning and 𝛾-ray Radiography

  • Kim, Da Sol;Jo, Young Hoon;Huh, Il Kwon;Byun, Sung Moon
    • Journal of Conservation Science
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    • v.38 no.1
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    • pp.55-63
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    • 2022
  • The Bigyeokjincheolloe (bomb shell), a scientific cultural heritage, has outstanding historical value for sustaining a gunpowder weapon of Joseon. In this study, the bomb shell was modeled through three-dimensional (3D) scanning centered on the external shape and 𝛾-ray radiography-based on the internal shape. In particular, to improve the contrast in the radiographic image, optimization and image processing were performed. After these processes, the thickness of the inner wall (2.5 cm on average) and the positions of the three mold chaplets were clearly revealed. For exhibition purposes, the 3D model of the bomb shell was output to a 3D printer and the output was rendered realistic by coloring. In addition, the internal functional elements, such as Mokgok, fuse, mud, gunpowder, and caltrops, were reproduced through handwork. The results will contribute to the study of digital heritages in two ways. First, the internal and external shapes of the bomb shell were modeled by fusing two different technologies, namely, 3D scanning and 𝛾-ray radiography. Second, the internal shape of the bomb shell was constructed from the original form data and the reproduction was utilized for museum exhibitions. The developed modeling approach will greatly expand the scope of museum exhibitions, from those centered on historical content to those centered on scientific content.

A Study on Quantitative Thickness Evaluation Using Film Density Variation in Film Radiography (Film Radiography에서 농도차를 이용한 정량적 두께 평가에 관한 연구)

  • Lee, Sung-Sik;Lee, Jeong-Ki;Kim, Young-H.
    • Journal of the Korean Society for Nondestructive Testing
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    • v.19 no.5
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    • pp.356-362
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    • 1999
  • Based on the assumption that film density increases exponentially with exposure in the industrial radiographic film. an equation representing the characteristic curves of industrial radiographic films and a new density-thickness relation are suggested. The accuracy and reliability of the suggested relation has been tested using radiographs of a carbon steel step wedge with known thickness variation by polychromatic X-ray and ${\gamma}$-ray ($Ir^{192}$). The experimental results were well agreed to the proposed relation in the range of film densities from 1.0 to 3.5 and it was more accurate than the conventional relation. It is also found that ${\gamma}$-ray is more effective in this purpose than polychromatic X-ray, which results in variation of effective linear absorption coefficient due to beam hardening effect as thickness increases. Therefore using the equation and experimentally determined parameters the quantitative evaluation of thickness variation is possible and it can be used to evaluate the depth of local corrosion of pressure vessels in plants.

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Development of Real-Time Thickness Measuring System for Insulated Pipeline Using Gamma-ray (감마선을 이용한 단열배관의 실시간 두께측정시스템 개발)

  • Jang, Ji-Hoon;Kim, Byung-Joo;Kim, Gi-Dong;Cho, Kyung-Shik
    • Journal of the Korean Society for Nondestructive Testing
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    • v.22 no.5
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    • pp.500-507
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    • 2002
  • By this study, on-line real-time radiometric system was developed using a 64 channels linear array of solid state detectors to measure wall thickness of insulated piping system. This system uses an Ir-192 as a gamma ray source and detector is composed of BGO scintillator and photodiode. Ir-192 gamma ray source and linear detector array mounted on a computer controlled robotic crawler. The Ir-192 gamma ray source is located on one side of the piping components and the detector array on the other side. The individual detectors of the detector array measure the intensity of the gamma rays after passing through the walls and the insulation of the piping component under measurement. The output of the detector array is amplified by amplifier and transmitted to the computer through cable. This system collects and analyses the data from the detector array in real-time as the crawler travels over the piping system. The maximum measurable length of pipe is 120cm/min. in the case of 1mm scanning interval.

방사성 동위원소를 이용한 문화재의 과학적보존 -고고유품 및 미술품의 조사감식법-

  • 김유선
    • Nuclear Engineering and Technology
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    • v.4 no.3
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    • pp.229-240
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    • 1972
  • Radioisotopes and their related techniques have recently been applied for scientific conservation works of cultural property and resulted many excellent findings or conservation data which could never be achieved by means of other techniques. Radiocarbon dating have widely been applied for dating the antique of organic origin, whereas the determination of radioactive contents in metal, ceramics, environmental soil, and classical objects could be able to afford many useful informations on the age, genuiness, and archeological significances as it had been produced. Trace quantity of contents of each antique have successfully been analyzed by means of radioactivation analysis or radio active tracer techniques, which could afford important technical data and results for tile conservation of each object. Radiography have also been applied for detecting the internal defects of metal objects and furthermore $\beta$-and ${\gamma}$-ray radiography were proved to be effective for such thin material as textile, painting, and fibres. In this article the detailed principle and procedures of each technique were presented so that the society could be able to make efforts to familiarize all concerns with these modern trends of the conservation techniques of cultural property.

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Comparison of Non-Destructive Testing Images using $^{192}Ir$ and $^{75}Se$ with Computed Radiography System (Computed Radiography 시스템에 $^{192}Ir$$^{75}Se$ 동위원소를 적용하여 촬영한 비파괴검사 영상 비교)

  • Kang, Sang-Mook;Chol, Chang-Il;Lee, Seung-Kyu;Park, Sang-Ki;Kim, Yong-Kyun
    • Journal of Radiation Protection and Research
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    • v.35 no.1
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    • pp.26-33
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    • 2010
  • A computed Radiography (CR) system by use of reusable Image Plate (IP) offers a convenient and reliable way to replace a conventional film-screen system for NDT (non-destructive testing) field. The quality of a radiography to detect a defect of welded objects depends on the procedure embracing several factors such as measurement conditions, image plate type/class, radiation energy, radiation type, and source to image plate distance. Also, the ability of images to detect a flaw reduces with increasing object thickness. In the study, the properties of gamma ray source were summarized for NDT field and inspection images of CR image system manufactured by FUJI were acquired using $^{75}Se$ and $^{192}Ir$ with welded objects. We analyzed the gray scale of hole defect image by using XCAP image processing program and calculated the image contrast and SNR in definition. Also the sesitivities of image quality indicator(IQI) were calculated for hot and cooling tube image of $^{75}Se$ and $^{192}Ir$.

A Study on the Evaluation of Radiation Safety in Opened-Ceiling-Facilities for Radiography Testing (천장 개방형 RT 사용시설의 방사선 안전성 평가 연구)

  • Sung-Hoe, Heo;Won-Seok, Park;Seung-Uk, Heo;Byung-In, Min
    • Journal of the Korean Society of Radiology
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    • v.16 no.6
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    • pp.741-749
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    • 2022
  • Radiography-Testing that verify the quality of welding structures without destruction are overwhelmingly used in industries, but many safety precautions are required as radiation is used. The workers for Radiography-Testing perform the inspection by moving the Iridium-192 radiation source embedded in the transport container of the gamma-ray irradiator within or outside the facility. The general facility is completely blocked about radiation from the outside with thick concrete, but if it is difficult for worker to handle object of inspection, facilities ceiling can be opened. A general facility may be constructed using a theoretical dose evaluation method because all exterior facilities are blocked, but if the ceiling is open, it is not appropriate to evaluate radiation safety with a simple theoretical calculation method due to the skyshine effect. Therefore, in this study, the radiation safety of the facility was evaluated in the actual field through an ion chamber survey-meter and an accumulated dose-meter called as OSLD, and the actual evaluation environment was modeled and evaluated using the Monte Carlo simulation code as FLUKA. According to the direction of the irradiation, the radiation dose at the facility boundary was difficult to meet the standards set by the regulatory authority, and radiation safety could be secured through additional methods. In addition, it was confirmed that the simulation results using the Iridium-192 source were valid evaluation with the actual measured results.

The Protective Effect of Chondroitin from Raja kenojei Cartilage on Collagen-induced Arthritis in DBA/1J Mice

  • Jin, Cheng-Hao;Yang, Ung;Kim, Song-Hee;Ryu, Jae-Won;Lee, Jae-Chang;Lee, Dong-Seok;Lee, Tae-Hoon
    • Food Science and Biotechnology
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    • v.16 no.4
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    • pp.594-599
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    • 2007
  • In this study, we evaluated whether the oral administration of chondroitin from the cartilage of Raja kenojei is effective on the progression of rheumatoid arthritis (RA), using collagen-induced arthritic (CIA) mice. Arthritis development was delayed dose-dependently in the chondroitin-treated groups. The pre- and late-treated groups receiving 1,000 mg/kg of chondroitin had clinical scores that were reduced significantly by 56.9 (p<0.05) and 43.3% (p<0.05), respectively, compared to the vehicle-treated groups. Hematoxylin eosin staining and X-ray radiography showed that the chondroitins reduced the infiltration of inflammatory cells and prevented joint destruction of the knee and paw. Reverse transcription-polyerase chain reaction analysis revealed that chondroitin administration inhibited the expressions of tumor necrosis $factor-{\alpha}$ ($TNF-{\alpha}$), $interlukin-1{\beta}$ ($IL-1{\beta}$), and $interferon-{\gamma}$ ($IFN-{\gamma}$) in joints more than the administration of vehicle. Chondroitin treatment also decreased the production of rheumatoid factors (RF), IgG and IgM, in the serum of CIA mice. These results indicate that chrondroitin administration has a protective effect involving the inhibition of pro-inflammatory cytokine production in CIA mice.

Study on the effect of long-term high temperature irradiation on TRISO fuel

  • Shaimerdenov, Asset;Gizatulin, Shamil;Dyussambayev, Daulet;Askerbekov, Saulet;Ueta, Shohei;Aihara, Jun;Shibata, Taiju;Sakaba, Nariaki
    • Nuclear Engineering and Technology
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    • v.54 no.8
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    • pp.2792-2800
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    • 2022
  • In the core of the WWR-K reactor, a long-term irradiation of tristructural isotopic (TRISO)-coated fuel particles (CFPs) with a UO2 kernel was carried out under high-temperature gas-cooled reactor (HTGR)-like operating conditions. The temperature of this TRISO fuel during irradiation varied in the range of 950-1100 ℃. A fission per initial metal atom (FIMA) of uranium burnup of 9.9% was reached. The release of gaseous fission products was measured in-pile. The release-to-birth ratio (R/B) for the fission product isotopes was calculated. Aspects of fuel safety while achieving deep fuel burnup are important and relevant, including maintaining the integrity of the fuel coatings. The main mechanisms of fuel failure are kernel migration, silicon carbide corrosion by palladium, and gas pressure increase inside the CFP. The formation of gaseous fission products and carbon monoxide leads to an increase in the internal pressure in the CFP, which is a dominant failure mechanism of the coatings under this level of burnup. Irradiated fuel compacts were subjected to electric dissociation to isolate the CFPs from the fuel compacts. In addition, nondestructive methods, such as X-ray radiography and gamma spectrometry, were used. The predicted R/B ratio was evaluated using the fission gas release model developed in the high-temperature test reactor (HTTR) project. In the model, both the through-coatings of failed CFPs and as-fabricated uranium contamination were assumed to be sources of the fission gas. The obtained R/B ratio for gaseous fission products allows the finalization and validation of the model for the release of fission products from the CFPs and fuel compacts. The success of the integrity of TRISO fuel irradiated at approximately 9.9% FIMA was demonstrated. A low fuel failure fraction and R/B ratios indicated good performance and reliability of the studied TRISO fuel.

Development of $^{192}Ir$ Small-Focal Source for Non-Destructive Testing Application by Using Enriched Target Material (고농축 표적을 이용한 비파괴검사용 $^{192}Ir$ 미세초점선원 개발)

  • Son, K.J;Hong, S.B.;Jang, K.D.;Han, H.S.;Park, U.J.;Lee, J.S.;Kim, D.H.;Han, K.D.;Park, C.D.
    • Journal of the Korean Society for Nondestructive Testing
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    • v.27 no.1
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    • pp.31-37
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    • 2007
  • A $^{192}Ir$ small-focal source has been developed by using the HANARO reactor and the radioisotope production facility at the Korea Atomic Energy Research Institute (KAERI). The small-focal source with the dimension of 0.5 mm in diameter and 0.5 mm in length was fabricated as an aluminum-encapsulated form by a specially designed pressing equipment. For the estimation of the radioactivity, neutron self-shielding and ${\gamma}-ray$ self-absorption effects on the measured activity was considered. From this estimation, it is realized that $^{192}Ir$ small-focal sources over 3 Ci activities can be produced from the HANARO. Field performance tests were performed by using a conventional source and the developed source to take images of a computer CPU and a piece of a carbon steel. The small-focal source showed better penetration sensitivity and geometrical sharpness than the conventional source does. It is concluded from the tests that the focal dimension of this source is small enough to maximize geometrical sharpness in the image taking for the close proximity shots, pipeline crawler applications and contact radiography.